MECHANICAL DESIGN ASPECTS OF THE FASTENING GUIDING SUPPORT SYSTEM FOR THE TOKAMAK FIRST WALL COMPONENTS SUBJECTED TO PLASMA DISRUPTION EVENTS
The effects of plasma disruption events on the structural integrity of the Tokamak inboard and outboard first wall foreseen for NET (Next European Torus) are investigated. The choice and position of the fastening and guiding support system combined with the strengthening of the back plate and of the vertical extensions can have a major impact on their integrity. The transient nature of the electromagnetic-type phenomena and the complex multilayer structure of the internal components, including different conducting materials, requires a fully three-dimensional dynamic analysis, based on a thin shell formulation, for both the electrical and mechanical computations. The present paper considers detailed mechanical design aspects of the inboard and outboard first wall segments, such as the choice for the support system position combined with additional stiffening of the rear part. The proper solution through the comparative study of various options is described.
Bibliographic Reference: SMIRT-10 (STRUCTURAL MECHANICAL IN REACTOR TECHNOLOGY), ANAHEIM, CA. (USA), AUG. 14-22, 1989, AVAILABILITY: CEC-LUXEMBOURG, DG-XIII-C-3, POB 1907, MENTIONING PAPER EN 34205 ORA
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Record Number: 1989126105100 / Last updated on: 1989-06-01
Available languages: en